ML051030209
| ML051030209 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/27/2004 |
| From: | Hynes C FirstEnergy Nuclear Operating Co |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| References | |
| Download: ML051030209 (23) | |
Text
Appendix C Job Performance Measure F O ES-C-1
~
Worksheet Facility: BVPS Unit 2 Task No.: 1350-004-03-023 Task
Title:
Terminate an Emerclencv Classification JPM No.: 2005 NRC SRO Admin No. 5 WA
Reference:
2.4.40 (4.0)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testinq, Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: . An Unusual Event was declared at Unit 2 due to indications of an RCS
-- . leak inside containment.
The unidentified leak rate was estimated to be between 12 and 20 gpm based on charging/letdown mismatch.
. A plant shutdown was initiated at 2% per minute.
The shutdown was completed and the plant is currently in Mode 5 with the RCS depressurized.
Task Standard: Emergency Plan EAL's reviewed and classification level terminated.
Required Materials: None General
References:
EPP/I-1a, Unit 2 - Recognition And Classification Of Emergency Conditions, Rev. 5 1/2-EPP-1-2, Unusual Event, Rev. 20 Handouts: EPP/I-1 b, Unit 2 - Recognition And Classification Of Emergency Conditions, Rev. 5 1/2-EPP-1-2, Unusual Event, Rev. 20 Initiating Cue: As the Emergency Director, you are to perform a review of the Emergency Plan EAL's and determine the current status of the Emergency Plan classification level. Report your results when finished.
Time Critical Task: No
-- Validation Time: 5 minutes BVPS-2 NRC ADMIN NO. 5 NUREG 1021, Revision 9
Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION 2005 NRC ADMIN NO. 5 (Denote Critical Steps with a check mark)
START TIME:
Performance Step: 1 Review the EAL's.
Standard: Candidate locates TAB 2.5, RCS Unidentified Leakage.
Standard: Candidate determines that the Unusual Event can be terminated based on Mode 5 and RCS depressurized.
NOTE: Candidate may also refer to 1/2-EPP-I-2, Unusual Event for guidance. If requested provide the Candidate with a copy of the procedure.
NOTE: If asked, inform the Candidate that it will not be necessary to refer to the event termination procedure, once the determination has been made that the event conditions no longer exist.
Com ment :
Terminating Cue: When the Candidate determines the Unusual Event can be terminated, the evaluation for this JPM is complete.
STOP TIME:
BVPS-2 NRC ADMIN NO. 5 NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: BVPS Unit 2 Task No.: 1300-009-03-023 Task
Title:
Review a Gaseous Waste Discharae JPM No.: 2005 NRC SRO Authorization Admin No. 4 WA
Reference:
2.3.8 (3.2)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing Simulated Performance: Actual Performance: X Class room X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The plant is in Mode 1 at 100% power. A gaseous waste discharge has
- been performed from [2GWS-TK25BIl Gaseous Waste Storage Tank on the previous shift.
Task Standard: RWDA-G reviewed and errors identified.
Required Materials: None General
References:
1/20M-19.4A.B, Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent, Rev. 12 Handouts: 1/20M-19.4A.B, Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent, Rev. 12 1/2-HPP-3.006.FO1, Gaseous Radioactive Waste Discharge Authorization (Modified)
Initiating Cue: As the Unit Supervisor, you are to perform a post-release review of the attached RWDA-G to verify that all of the data entered is complete and correct. Report your results when finished.
Time Critical Task: No Validation Time: 16 minutes BVPS-2 NRC ADMIN NO. 4 NUREG 1021, Revision 9
Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION 2005 NRC ADMlN NO 4
\. - (Denote Critical Steps with a check mark)
START TIME:
4 PerformanceStep: 1 Review the RWDA-G for correct entries and completeness.
Standard:
(Step 1II.J. Note) .
Candidate identifies the following errors:
Chemistry signature is missing in the pre-discharge authorization (Step IV.A.9 Note) . section.
Discharge Start date exceeds the effective date (greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />).
NOTE: Candidate may refer to 1/20M-19.4A.B, Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent procedure in order to verify accuracy and completeness of the RWDA-G.
Comment :
Terminating Cue: When the Candidate identifies the errors contained in the RWDA-G, the evaluation for this JPM is complete.
STOP TIME:
BVPS-2 NRC ADMIN NO. 4 NUREG 1021, Revision 9
Appendix C Job performance Measure Form ES-C-1 Worksheet Facility: BVPS Unit 2 Task No.:
Task
Title:
Determine Maximum Allowable Stav Time JPM No.: 2005 NRC RO Admin No. 4 WA
Reference:
2.3.10 (2.9)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testina:
Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: Both Units are operating at 100% power. A void has developed in the suction line to 1CH-P-1A, Charging Pump at Unit 1 , You are NOT currently signed on to fill any operator positions. Your current TEDE dose for the quarter is 150 mR.
Task Standard: Determine the correct RWP and the maximum stay time according to the survey map dose rates.
Required Materials: None General Refe rences: 1/2-ADM-1630, Radiation Worker Practices, Rev. 8 Handouts: Set of RWPs Radiation Survey Map 102182 Initiating Cue: You are to assist a QC Inspector in performing an ultrasonic examination of the void. This requires selecting the correct RWP to enter the RCA, and calculating your MAXIMUM stay time in the charging pump room based on the radiation readings from a survey map. Report your results when finished.
Time Critical Task: NO Validation Time: 7 minutes BVPS-2 NRC ADMIN NO. 4 NUREG 1021, Revision 9
Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION 2005 NRC ADMIN NO. 4 (Denote Critical Steps with a check mark)
START TIME:
.( Performance Step: 1 Select correct RWP.
Standard: Candidate correctly determines to log in under RWP 104-1003 based on < 100 mWhr. General Area Range and EAD dose alarm setpoints of 100 mR.
CUE: Provide the Candidate with the set of RWPs.
Comment:
NOTE: After selecting an RWP, provide the Candidate with the attached Survey Map to complete the following step.
4 Performance Step: 2 Calculate maximum stay time.
Standard: Candidate correctly calculates maximum stay time as 2 hrs 100 mR - 50 mWhr. - 2 hrs.
(EAD dose limit) (highest dose rate) (Stay time)
Comment:
Terminating Cue: When the Candidate reports the results, the evaluation for this JPM is complete.
STOP TIME:
BVPS-2 NRC ADMIN NO. 4 NUREG 1021, Revision 9
Appendix C Job Performance Measure F o ES-C-1
~
Worksheet FaciIity : BVPS Unit 2 Task No.: 1300-023-03-023 Task
Title:
Amrove a Taaaina Request JPM No.: 2005 NRC SRO Admin No. 3 WA
Reference:
2.2.13 (3.8)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testinq Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The plant is operating at 100% power with all systems in their normal operating alignment. A tagout section has been prepared to isolate and drain [2QSS*P22A], Refueling Water Cooling Pump for maintenance.
Task Standard: Review a clearance tagout section and identify errors.
Required Materials: None General
References:
NOP-OP-1001, Clearancenagging Program, Rev. 4 Handouts: Tagging Section with errors 20M-13.3.6.1, Valve List - 2QQS, Rev. 9 20M-13.3.C, Power Supply And Control Switch List, Issue 4, Rev. 7 OP Manual Fig. No. 13-2, Quench Spray System, Rev. 13 NOP-OP-1001, Clearancenagging Program, Rev. 4 Initiating Cue: The Shift Manager directs you to conduct a review of the attached tagout section that is ready for approval for completeness and accuracy Report your results when finished.
Time Critical Task: Yes Validation Time: 12 minutes BVPS-2 NRC ADMIN NO. 3 NUREG 1021, Revision 9
Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION 2005 NRC ADMIN NO. 3 (Denote Critical Steps with a check mark)
START TIME:
NOTE: This task is normally performed using the eSOMS clearance computer and signed electronically. If necessary, for the purpose of this JPM, inform the Candidate to review a hardcopy of the tagout for approval in place of performing an electronic review.
4 Performance Step: 1 Review the tagout section for accuracy and completeness Standard: Candidate verifies tagout section is appropriate for the task.
Standard:
Candidate identifies and reports the following tagout errors:
Breaker MCC-2-17-6C is tagged in the On position. The
. correct position is Off.
Valve 2QSS-21 is not a correct discharge isolation point
. (2QSS*P22B vs. P22A). The correct valve is 2QS-20.
Valve 2QSS-239 is tagged in the Shut position. The correct position is Open.
CUE: If the Candidate asks for direction following identification of the first error, direct the Candidate to review the remainder of the tagout section.
Comment:
Terminating Cue: When the Candidate reports the results of the review, the evaluation for this JPM is complete.
STOP TIME:
BVPS-2 NRC ADMIN NO. 3 NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: BVPS Unit 2 Task No.: 0481-0203-03-013 Task
Title:
Review a Taaainq Reauest JPM No.: 2005 NRC RO Admin No. 3 WA
Reference:
2.2.13 (3.8)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The plant is operating at 100% power with all systems in their normal operating alignment. A tagout section has been prepared to isolate and L-drain [2QSS*P22A], Refueling Water Cooling Pump for maintenance.
Task Standard: Correctly review a clearance tagout section and identify errors.
Required Materials: None General
References:
NOP-OP-1001, Clearancenagging Program, Rev. 4 Handouts: Tagging Section with errors 20M-13.3.B.1, Valve List - 2QQS, Rev. 9 20M-13.3.C, Power Supply And Control Switch List, Issue 4, Rev. 7 OP Manual Fig. No. 13-2, Quench Spray System, Rev. 13 NOP-OP-1001, Clearancenagging Program, Rev. 4 Initiating Cue: The Unit Supervisor directs you to conduct a review of the attached tagout section that is being prepared for use and determine its completeness and accuracy. Report your results when finished.
Time Critical Task: Yes Validation Time: 10 minutes BVPS-2 NRC ADMIN NO. 3 NUREG 1021, Revision 9
Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION 2005 NRC ADMIN NO. 3
__ (Denote Critical Steps with a check mark)
START TIME:
NOTE: This task is normally performed using the eSOMS clearance computer and signed electronically. If necessary, for the purpose of this JPM, inform the Candidate to review a hardcopy of the tagout in place of performing an electronic review.
J' Performance Step: 1 Review the tagout section for accuracy and completeness.
Standard: Candidate verifies tagout section is appropriate for the task.
Standard: Candidate identifies and reports the following tagout errors:
Valve 2QSS-21 is not a correct discharge isolation point (2QSS*P22B vs. P22A). The correct valve is 2QSS-20.
Valve 2QSS-239 is tagged in the Shut position. The correct position is Open.
CUE: If the Candidate asks for direction following identification of the first error, direct the Candidate to review the remainder of the tagout section.
Cornment:
r Terminating Cue: When the Candidate reports the results of the review, the evaluation for this JPM is complete.
STOP TIME:
BVPS-2 NRC ADMIN NO. 3 NUREG 1021, Revision 9
Appendix C Page 3 of 4 Form ES-C-1 V ERI FI CAT1ON OF COMPLETION 2005 NRC AOMIN NO. 3 JPM No.: 2005 NRC RO No. 3 Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Result: SatisfactoryAJnsatisfactory Examiner's Sianature: Date:
BVPS-2 NRC ADMIN NO. 3 NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: BVPS Unit 2 Task No.: 001 1-003-01-013 Task
Title:
Review an Estimated Critical Position JPM No.: 2005 NRC SRO Calculation Admin No. 2 WA
Reference:
192008 K1.07 (3.5) 2.1.23 (3.9)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testinq Simulated Performance: Actual Performance: X CI assroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: .. A plant startup is being performed 5 days after a reactor trip.
. Core bumup is 1,000 MWD/MTU.
The plant computer is NOT available.
Task Standard: Estimated critical boron concentration calculated within the specified tolerance and error@) identified.
Required Materials: Calculator; Evaluator ECP Answer Sheet General Refe rences: 20M-50.4. F, Performing An Estimated Critical Position Calculation, Rev. 4 BV-2 Curve Book Handouts: 20M-50.4.F, with Critical Data recorded in DATA SHEET 1 BV-2 Curves CB-12,21122,23,24A- C Initiating Cue: The Shift Manager directs you to review an ECP calculation and determine the boron concentration for startup in accordance with 20M-50.4. F, Performing An Estimated Critical Position Calculation.
Time Critical Task: No Validation Time: 24 minutes BVPS-2 NRC ADMIN NO.2 NUREG 1021, Revision 9
Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION 2005 NRC ADMIN NO. 2 (Denote Critical Steps with a check mark)
START TIME:
4 Performance Step: 1 Review the ECP calculation.
(Data Sheet 1)
Standard: Candidate correctly determines the critical boron concentration required for startup within k 5 ppm.
Standard: Candidate correctly identifies errors as noted on Evaluator's ECP Answer Sheet.
Comment:
Terminating Cue: When the Candidate completes the calculation, the evaluation for this JPM is complete. I STOP TIME:
BVPS-2 NRC ADMIN NO. 2 NUREG 1021, Revision 9
Appendix C Page 3 of 4 Form ES-C-1 VERIFICATION OF COMPLETION 2005 NRC ADMIN NO. 2 JPM No.: 2005 NRC SRO No. 2 Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
L Question:
Response
Result: Satisfactory/Unsatisfactory Examiner's Signature: Date:
BVPS-2 NRC ADMIN NO. 2 NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: BVPS Unit 2 Task No.: 001 1-003-01-013 Task
Title:
Perform an Estimated Critical Position JPM No.: 2005 NRC RO Calculation Admin No. 2 WA
Reference:
192008 K1.07 (3.5) 2.1.23 (3.9)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testinq Simulated Performance: Actu aI Performance : X Class room X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: . A plant startup is being performed 5 days after a reactor trip from
--~
.. 100% power.
Core burnup is 1,000 MWD/MTU.
. RCS boron concentration is 1425 ppm.
The plant computer is NOT available.
Task Standard: Estimated critical boron concentration calculated within the specified tolerance and error(s) identified.
Required Materials: Calculator; Evaluator ECP Answer Sheet General
References:
20M-50.4.F, Performing An Estimated Critical Position Calculation, Rev. 4 BV-2 Curve Book Handouts: 20M-50.4.F, with Critical Data recorded in DATA SHEET 1 BV-2 Curves CB-l2,21,22,23,24A - C Initiating Cue: The Unit Supervisor directs you to perform a review of an ECP calculation and determine that the critical boron concentration is correct using 20M-50.4.F, Performing An Estimated Critical Position Calculation.
Time Critical Task: No Validation Time: 12 minutes L
BVPS-2 NRC ADMIN NO. 2 NUREG 1021, Revision 9
Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION 2005 NRC ADMIN NO. 2
- (Denote Critical Steps with a check mark)
START TIME:
4 Performance Step: 1 Calculate ECP.
(Data Sheet 1)
Standard: Candidate correctly determines critical boron concentration using 20M-50.4.F within k 5 ppm.
Standard: Candidate correctly identifies errors as noted on Evaluator's ECP Answer Sheet.
Cornment :
Terminating Cue: When the Candidate completes the calculation, the evaluation for this JPM is complete.
STOP TIME:
BVPS-2 NRC ADMIN NO. 2 NUREG 1021, Revision 9
Appendix C Page 3 of 4 F o ES-C-1
~
VERIFICATION OF COMPLETION 2005 NRC ADMIN NO. 2 JPM No.: 2005 NRC RO No. 2 Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
R esuIt : Satisf acto ry/ Unsat isf acto ry Examiner's Signature: Date:
BVPS-2 NRC ADMIN NO. 2 NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet FaciIity: BVPS Unit 2 Task No.: 1320-008-03-023 Task
Title:
Determine Action Reauired For Failed AC JPM No.: 2005 NRC SRO Sou rces Surveillance Admin No. 1 WA
Reference:
2.2.12 (3.4)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testinq, Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The plant is operating at 100% power with all systems in their normal operating alignment. The 2-1 EDG was declared inoperable and removed from service 30 minutes ago due to a ruptured engine cylinder. The PO has completed 20ST-36.7, Offsite to Onsite Power Distribution System Breaker Alignment Verification.
Task Standard: Procedure errors are identified and Technical Specification action requirements are determined for a failed surveillance test.
Required Materials: None General
References:
20ST-36.7, Offsite To Onsite Power Distribution System Breaker Alignment Verification, Rev. 8 BVPS Unit 2 Technical Specifications LCO 3.8.1.1 Handouts: 20ST-36.7, Offsite To Onsite Power Distribution System Breaker Alignment Verification, Rev. 8 (marked up copy)
BVPS Unit 2 Technical Specifications LCO 3.8.1.1 Initiating Cue: The Shift Manager directs you to review the completed 20ST-36.7, Offsite To Onsite Power Distribution System Breaker Alignment Verification for completeness. Report your results when finished.
Time Critical Task: No Validation Time: 14 minutes BVPS-2 NRC ADMIN NO. 1 NUREG 1021, Revision 9
Appendix C Page 2 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2005 NRC ADMIN NO. 1 (Denote Critical Steps with a check mark)
START TIME:
.( Performance Step: 1 Review procedure for completeness.
Standard: Candidate determines that signoffs are missing for the following steps:
VI.D.l (Operator performing test has reviewed procedure)
VII.A.l .b (Class 1E power through the USST's or SSST's)
Cornment :
.( Performance Step: 2 Review Data Sheet 1 for completeness.
Standard: Candidate determines that the neon light for 4KV breaker ACB 3425 is marked as OFF.
NOTE: This is the required lineup for live bus transfer that would be indicated if the neon light was ON.
Comment:
BVPS-2 NRC ADMIN NO. 1 NUREG 1021, Revision 9
Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2005 NRC ADMIN NO. 1 Performance Step: 3 Determine Technical Specification Action Statement requ irements .
Standard: Candidate determines that OST does not satisfy the Acceptance Criteria.
Standard: Candidate identifies applicability of T.S. Action Statement 3.8.1.1.c with one offsite circuit and one diesel generator inoperable.
NOTE: Provide the Candidate with a copy of the T.S.
handout.
NOTE: Refer to attached Technical Specification LCO 3.8.1.1 Action c for applicable requirementsfor an inoperable offsite circuit and diesel generator.
Cornment :
I Terminating Cue: When the Candidate identifies the Technical Specification action statement requirement, the evaluation for this JPM is complete.
STOP TIME:
BVPS-2 NRC ADMIN NO. 1 NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: BVPS Unit 2 Task No.: 0481-014-03-013 Task
Title:
Perfom RCS Cooldown Verification JPM No.: 2005 NRC RO Admin No. 1 WA
Reference:
2.1.25 (2.8)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testinq Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: A plant shutdown to Mode 5 is in progress.
Current RCS wide range temperature and pressure are 138°F and 1,120 psig respectively.
Data Sheet 3: RCS Cooldown Determination is in effect to track RCS cooldown limits per 20M-52.4.R.1.F, Refueling Station Shutdown From 100% Power To Mode 5.
Task Standard: RCS cooldown rate calculated and verified NOT to be within acceptable limits.
Required Materials: Calculator General
References:
20M-52.4.R.l .F, Refueling Station Shutdown From 1000/0 Power To Mode 5, Rev. 1 Handouts: Data Sheet 3: RCS Cooldown Determination (Modified with entries) 20M-52.4.R.1 .F, Attachment 18: RCSIPRZR COOLDOWN SURVEILLANCES Figure 51-2, BV-2 Reactor Coolant System Cooldown Limitations Initiating Cue: The Unit Supervisor directs you to complete the information required for the 1100 hour0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> entry of Data Sheet 3, RCS Cooldown Determination and verify the RCS cooldown is within acceptable limits using Attachment 18, RCS/PRZR Cooldown Surveillances. Report your results when finished.
Time Critical Task: No
\- Validation Time: 8 minutes BVPS-2 NRC ADMIN NO.1 NUREG 1021, Revision 9
Appendix C Page 2 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2005 NRC ADMIN NO 1 (Denote Critical Steps with a check mark)
START TIME:
4 Performance Step: 1 Calculate the RCS cooldown rate at least once per 30 minutes during (Step A.l) system cooldown using the following equation AND Record the results on Data Sheet 3:
COOLDOWN RATE = {TEMPf -TEMPI) X 60 MIN/HR CHANGE IN TIME Standard: Candidate correctly calculates current RCS cooldown rate as 40"F/hr.
{138"F - 158°F) x 60 = - 40°F 30 Comment:
PerformanceStep: 2 Verify the RCS cooldown rate is I 100 F/HR at least once per 30 (Step A.2) minutes during system cooldown.
Standard: Candidate determines RCS cooldown rate is within the acceptable limit of less than or equal to 1OO"/hr.
Comment:
BVPS-2 NRC ADMIN NO. 1 NUREG 1021, Revision 9
Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2005 NRC ADMIN NO. 1 4 Performance Step: 3 Verify RCL A(B)(C) Cold Leg Temp or RHS Inlet Temp AND RCS WR Pressure are within the Acceptable Operation region of 20M-(Step A.3) 51.5 Figure 51-2, Reactor Coolant System Cooldown Limitations at least once per 30 minutes during system cooldown AND Record the results on Data Sheet 3:
Standard: Candidate determines that current RCS temperature and pressure are NOT within the acceptable region of Figure 51-2.
Standard: Candidate reports the results to the Unit Supervisor.
Comme nt :
Terminating Cue: When the Candidate reports the results of the cooldown determination, the evaluation for this JPM is complete.
STOP TIME:
BVPS-2 NRC ADMIN NO. 1 NUREG 1021, Revision 9